Source term experiments project (STEP): aerosol characterization system

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:5918877

Schlenger, B J; Dunn, P F

A series of four experiments is being conducted at Argonne National Laboratory's TREAT Reactor. They have been designed to provide some of the necessary data regarding magnitude and release rates of fission products from degraded fuel pins, physical and chemical characteristics of released fission products, and aerosol formation and transport phenomena. These are in-pile experiments, whereby the test fuel is heated by neutron induced fission and subsequent clad oxidation in steam environments that simulate as closely as practical predicted reactor accident conditions. The test sequences cover a range of pressure and fuel heatup rate, and include the effect of Ag/In/Cd control rod material.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5918877
• Report Number(s): CONF-850406-5; ON: DE85010248
• Resource Relation: Conference: International symposium and workshop on particulate and multi-phase processes and the 16th annual meeting of the Fine Particle Society, Miami Beach, FL, USA, 22 Apr 1985
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR ACCIDENTS
FISSION PRODUCT RELEASE
TREAT REACTOR
AEROSOLS
FUEL PINS
SAMPLERS
SAMPLING
SPENT FUEL ELEMENTS
STEAM
ACCIDENTS
AIR COOLED REACTORS
COLLOIDS
DISPERSIONS
ENRICHED URANIUM REACTORS
EQUIPMENT
EXPERIMENTAL REACTORS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
SOLS
TEST REACTORS
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors